SFCOMPO-2.0: An OECD NEA database of spent nuclear fuel isotopic assays, reactor design specifications, and operating data

Michel-Sendis, F.; Gauld, I.; Martinez, J. S.; Alejano, C.; Bossant, M.; Boulanger, D.; Cabellos, O.; Chrapciak, V.; Conde, J.; Fast, I.; Gren, M.; Govers, K.; Gysemans, M.; Hannstein, V.; Havlůj, F.; Hennebach, M.; Hordosy, G.; Ilas, G.; Kilger, R.; Mills, R.; Mountford, D.; Ortego, P.; Radulescu, G.; Rahimi, M.; Ranta-Aho, A.; Rantamäki, K.; Ruprecht, B.; Soppera, N.; Stuke, M.; Suyama, K.; Tittelbach, S.; Tore, C.; Winckel, S. Van; Vasiliev, A.; Watanabe, T.; Yamamoto, Toru; Yamamoto, Toshihisa

doi:10.1016/j.anucene.2017.07.022

Title: SFCOMPO-2.0: An OECD NEA database of spent nuclear fuel isotopic assays, reactor design specifications, and operating data

Abstract

SFCOMPO-2.0 is the new release of the Organisation for Economic Co-operation and Development (OECD) Nuclear Energy Agency (NEA) database of experimental assay measurements. These measurements are isotopic concentrations from destructive radiochemical analyses of spent nuclear fuel (SNF) samples. We supplement the measurements with design information for the fuel assembly and fuel rod from which each sample was taken, as well as with relevant information on operating conditions and characteristics of the host reactors. These data are necessary for modeling and simulation of the isotopic evolution of the fuel during irradiation. SFCOMPO-2.0 has been developed and is maintained by the OECD NEA under the guidance of the Expert Group on Assay Data of Spent Nuclear Fuel (EGADSNF), which is part of the NEA Working Party on Nuclear Criticality Safety (WPNCS). Significant efforts aimed at establishing a thorough, reliable, publicly available resource for code validation and safety applications have led to the capture and standardization of experimental data from 750 SNF samples from more than 40 reactors. These efforts have resulted in the creation of the SFCOMPO-2.0 database, which is publicly available from the NEA Data Bank. Our paper describes the new database, and applications of SFCOMPO-2.0 for computer code validation, integralmore »« less

Authors:

Michel-Sendis, F. ^[1]; Gauld, I. ^[2]; Martinez, J. S. ^[2]; Alejano, C. ^[3]; Bossant, M. ^[1]; Boulanger, D. ^[4]; Cabellos, O. ^[1]; Chrapciak, V. ^[5]; Conde, J. ^[6]; Fast, I. ^[7]; Gren, M. ^[8]; Govers, K. ^[9]; Gysemans, M. ^[9]; Hannstein, V. ^[10]; Havlůj, F. ^[8]; Hennebach, M. ^[11]; Hordosy, G. ^[12];

^[2]; Kilger, R. ^[10]; Mills, R. ^[13] more »

Organisation for Economic Co-operation and Development (OECD), Boulogne-Billancourt (France)
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Nuclear Safety Council, Madrid (Spain)
National Organization for Radioactive Waste and Enriched Fissile Fuel (NIRAS/ONDRAF), Bussels (Belgium)
Vuje, Inc., Trnava (Slovak Republic)
ENUSA Industries, Madrid (Spain)
Julich Research Centre (Germany)
Nuclear Research Inst., Rez (Czech Republic)
Belgian Nuclear Research Center (SCK-CEN), Mol (Belgium)
Society for Plant and Reactor Safety (GRS), Munich (Germany)
AREVA GmbH, Erlangen (Germany)
Centre for Energy Research Hungarian Academy of Sciences, Budapest (Hungary)
UK National Nuclear Lab., Cumbria (United Kingdom)
UK National Nuclear Lab., Sellafield (United Kingdom)
Engineering and Analysis of Shields (SEA), Madrid (Spain)
US Nuclear Regulatory Commission (NRC), Rockville, MD (United States)
Industrial Power Corporation (TVO), Helsinki (Finland)
Radiation and Nuclear Safety Authority (STUK), Helsinki (Finland)
Federal Office for Radiation Protection (BFS), Salzgitter (Germany)
Japan Atomic Energy Agency (JAEA), Ibaraki (Japan)
Scientific Engineering Consultants GmbH (WTI), Julich (Germany)
Joint Research Centre Karlsruhe, Eggenstein-Leopoldshafen (Germany)
Paul Scherrer Inst. (PSI), Villigen (Switzerland)
Japan Atomic Energy Agency (JAEA), Tokai (Japan)
Nuclear Regulation Authority, Tokyo (Japan)

Publication Date:: Wed Aug 02 00:00:00 EDT 2017

Research Org.:: Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

Sponsoring Org.:: USDOE

OSTI Identifier:: 1376611

Grant/Contract Number:: AC05-00OR22725

Resource Type:: Accepted Manuscript

Journal Name:: Annals of Nuclear Energy (Oxford)

Additional Journal Information:: Journal Name: Annals of Nuclear Energy (Oxford); Journal Volume: 110; Journal Issue: C; Journal ID: ISSN 0306-4549

Publisher:: Elsevier

Country of Publication:: United States

Language:: English

Subject:: 11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; 97 MATHEMATICS AND COMPUTING; SFCOMPO; Spent nuclear fuel database; Radiochemical assay data; Experimental isotopic compositions; Nuclear fuel depletion; Nuclear fuel evolution; Code validation; Integral benchmarks

Citation Formats


                    Michel-Sendis, F., Gauld, I., Martinez, J. S., Alejano, C., Bossant, M., Boulanger, D., Cabellos, O., Chrapciak, V., Conde, J., Fast, I., Gren, M., Govers, K., Gysemans, M., Hannstein, V., Havlůj, F., Hennebach, M., Hordosy, G., Ilas, G., Kilger, R., Mills, R., Mountford, D., Ortego, P., Radulescu, G., Rahimi, M., Ranta-Aho, A., Rantamäki, K., Ruprecht, B., Soppera, N., Stuke, M., Suyama, K., Tittelbach, S., Tore, C., Winckel, S. Van, Vasiliev, A., Watanabe, T., Yamamoto, Toru, and Yamamoto, Toshihisa. SFCOMPO-2.0: An OECD NEA database of spent nuclear fuel isotopic assays, reactor design specifications, and operating data.  United States: N. p., 2017. 
Web.  doi:10.1016/j.anucene.2017.07.022.

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                    Michel-Sendis, F., Gauld, I., Martinez, J. S., Alejano, C., Bossant, M., Boulanger, D., Cabellos, O., Chrapciak, V., Conde, J., Fast, I., Gren, M., Govers, K., Gysemans, M., Hannstein, V., Havlůj, F., Hennebach, M., Hordosy, G., Ilas, G., Kilger, R., Mills, R., Mountford, D., Ortego, P., Radulescu, G., Rahimi, M., Ranta-Aho, A., Rantamäki, K., Ruprecht, B., Soppera, N., Stuke, M., Suyama, K., Tittelbach, S., Tore, C., Winckel, S. Van, Vasiliev, A., Watanabe, T., Yamamoto, Toru, & Yamamoto, Toshihisa. SFCOMPO-2.0: An OECD NEA database of spent nuclear fuel isotopic assays, reactor design specifications, and operating data.  United States.  https://doi.org/10.1016/j.anucene.2017.07.022

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                    Michel-Sendis, F., Gauld, I., Martinez, J. S., Alejano, C., Bossant, M., Boulanger, D., Cabellos, O., Chrapciak, V., Conde, J., Fast, I., Gren, M., Govers, K., Gysemans, M., Hannstein, V., Havlůj, F., Hennebach, M., Hordosy, G., Ilas, G., Kilger, R., Mills, R., Mountford, D., Ortego, P., Radulescu, G., Rahimi, M., Ranta-Aho, A., Rantamäki, K., Ruprecht, B., Soppera, N., Stuke, M., Suyama, K., Tittelbach, S., Tore, C., Winckel, S. Van, Vasiliev, A., Watanabe, T., Yamamoto, Toru, and Yamamoto, Toshihisa. Wed .  
"SFCOMPO-2.0: An OECD NEA database of spent nuclear fuel isotopic assays, reactor design specifications, and operating data".  United States.  https://doi.org/10.1016/j.anucene.2017.07.022.  https://www.osti.gov/servlets/purl/1376611.

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@article{osti_1376611,

  title        = {SFCOMPO-2.0: An OECD NEA database of spent nuclear fuel isotopic assays, reactor design specifications, and operating data},

  author       = {Michel-Sendis, F. and Gauld, I. and Martinez, J. S. and Alejano, C. and Bossant, M. and Boulanger, D. and Cabellos, O. and Chrapciak, V. and Conde, J. and Fast, I. and Gren, M. and Govers, K. and Gysemans, M. and Hannstein, V. and Havlůj, F. and Hennebach, M. and Hordosy, G. and Ilas, G. and Kilger, R. and Mills, R. and Mountford, D. and Ortego, P. and Radulescu, G. and Rahimi, M. and Ranta-Aho, A. and Rantamäki, K. and Ruprecht, B. and Soppera, N. and Stuke, M. and Suyama, K. and Tittelbach, S. and Tore, C. and Winckel, S. Van and Vasiliev, A. and Watanabe, T. and Yamamoto, Toru and Yamamoto, Toshihisa},

  abstractNote = {SFCOMPO-2.0 is the new release of the Organisation for Economic Co-operation and Development (OECD) Nuclear Energy Agency (NEA) database of experimental assay measurements. These measurements are isotopic concentrations from destructive radiochemical analyses of spent nuclear fuel (SNF) samples. We supplement the measurements with design information for the fuel assembly and fuel rod from which each sample was taken, as well as with relevant information on operating conditions and characteristics of the host reactors. These data are necessary for modeling and simulation of the isotopic evolution of the fuel during irradiation. SFCOMPO-2.0 has been developed and is maintained by the OECD NEA under the guidance of the Expert Group on Assay Data of Spent Nuclear Fuel (EGADSNF), which is part of the NEA Working Party on Nuclear Criticality Safety (WPNCS). Significant efforts aimed at establishing a thorough, reliable, publicly available resource for code validation and safety applications have led to the capture and standardization of experimental data from 750 SNF samples from more than 40 reactors. These efforts have resulted in the creation of the SFCOMPO-2.0 database, which is publicly available from the NEA Data Bank. Our paper describes the new database, and applications of SFCOMPO-2.0 for computer code validation, integral nuclear data benchmarking, and uncertainty analysis in nuclear waste package analysis are briefly illustrated.},

  doi          = {10.1016/j.anucene.2017.07.022},

  journal      = {Annals of Nuclear Energy (Oxford)},

  number       = C,

  volume       = 110,

  place        = {United States},

  year         = {Wed Aug 02 00:00:00 EDT 2017},

  month        = {Wed Aug 02 00:00:00 EDT 2017}

}

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Works referenced in this record:

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Determination of Bandwidths of PWR-UO ₂ Spent Fuel Radionuclide Inventory Based on Real Operational History Data
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Validation of new depletion capabilities and ENDF/B-VII data libraries in SCALE
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Ilas, Germina; Gauld, Ian C.; Radulescu, Georgeta
Annals of Nuclear Energy, Vol. 46
DOI: 10.1016/j.anucene.2012.03.012

A method for including external feed in depletion calculations with CRAM and implementation into ORIGEN
journal, November 2015

Isotalo, A. E.; Wieselquist, W. A.
Annals of Nuclear Energy, Vol. 85
DOI: 10.1016/j.anucene.2015.04.037

Nuclide Composition Benchmark Data Set for Verifying Burnup Codes on Spent Light Water Reactor Fuels
journal, February 2002

Nakahara, Yoshinori; Suyama, Kenya; Inagawa, Jun
Nuclear Technology, Vol. 137, Issue 2
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Proposed re-evaluation of the 154Eu thermal $(n, γ)$ capture cross-section based on spent fuel benchmarking studies
journal, January 2017

Skutnik, Steven E.
Annals of Nuclear Energy, Vol. 99
DOI: 10.1016/j.anucene.2016.09.003

Re-evaluation of Assay Data of Spent Nuclear Fuel obtained at Japan Atomic Energy Research Institute for validation of burnup calculation code systems
journal, May 2011

Suyama, Kenya; Murazaki, Minoru; Ohkubo, Kiyoshi
Annals of Nuclear Energy, Vol. 38, Issue 5
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Williams, M. L.
Nuclear Science and Engineering, Vol. 70, Issue 1
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Works referencing / citing this record:

Flexible classification with spatial quantile comparison and novel statistical features applied to spent nuclear fuel analysis
journal, August 2018

Dayman, Kenneth J.; Weber, Charles F.
Journal of Radioanalytical and Nuclear Chemistry, Vol. 318, Issue 1
DOI: 10.1007/s10967-018-6067-y

Discrimination of weapons-grade plutonium from thermal reactors in nuclear forensics
journal, September 2019

Nikolaou, G.; Biegalski, S. R.
Journal of Radioanalytical and Nuclear Chemistry, Vol. 322, Issue 2
DOI: 10.1007/s10967-019-06810-4

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Title: SFCOMPO-2.0: An OECD NEA database of spent nuclear fuel isotopic assays, reactor design specifications, and operating data

Abstract

Citation Formats

SCALE 6: Comprehensive Nuclear Safety Analysis Code System journal, May 2011

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A method for including external feed in depletion calculations with CRAM and implementation into ORIGEN journal, November 2015

Nuclide Composition Benchmark Data Set for Verifying Burnup Codes on Spent Light Water Reactor Fuels journal, February 2002

Proposed re-evaluation of the 154Eu thermal n , γ capture cross-section based on spent fuel benchmarking studies journal, January 2017

Re-evaluation of Assay Data of Spent Nuclear Fuel obtained at Japan Atomic Energy Research Institute for validation of burnup calculation code systems journal, May 2011

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Determination of Bandwidths of PWR-UO ₂ Spent Fuel Radionuclide Inventory Based on Real Operational History Data
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journal, August 2012

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Proposed re-evaluation of the 154Eu thermal $(n, γ)$ capture cross-section based on spent fuel benchmarking studies
journal, January 2017

Re-evaluation of Assay Data of Spent Nuclear Fuel obtained at Japan Atomic Energy Research Institute for validation of burnup calculation code systems
journal, May 2011

Development of Depletion Perturbation Theory for Coupled Neutron/Nuclide Fields
journal, April 1979

Flexible classification with spatial quantile comparison and novel statistical features applied to spent nuclear fuel analysis
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